ML20032B192

Amend 7 to License NPF-9,revising Tech Specs to Change Instrumentation Setpoints,Correct Monitor Measurement Range & Revise Snubber Listings

ML20032B192
Person / Time
Site:	McGuire
Issue date:	10/27/1981
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20032B193	List: ML20032B192 ML20032B194 ML20032B195
References
TAC-46812, NUDOCS 8111050200
Download: ML20032B192 (53)

Text

DUKE POWER COMPANY DOCKET NO. 50-369 HCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 7 License No. NPF-9 1.

The Nuclear Reglatory Comission (the Comission) has found that:

)

A.

The application for amendment to the itcGuire Nuclear Station, Unit i (the facility) Facility Operating License No. NPF-9. filed by the Duke Power Company (licensee) dated August 12, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, ano the regulations of the Com-mission; C.

There is reasonable assurance: (1) that the activities luthorized by this amendr.ent can be conducted without endangering the health

)

and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations set forth j

in 10 CFR Chapter I; j

D.

The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the -

public; E.

The issuance of this arendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. HPF-9 is hereby amended to read as follows:

i 8111050200 811027 DR ADOCK 05000 (2) Technical Specifications p

The Technical Specifications contained in Appendix A, as revised through Amendaent No. 7, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technice! Specifications i

I and the Environcental Protection Plan.

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conuwe>

ocis)

[ NRC FORM 318 00-80) NRCM 024o OFFICIAL RECORD COPY usomi-mee0_j

Ys t 3.

This ticense atendixnt is effective as of its date of issuance.

FOR Tite NUCLEAR REGui.ATORY CottilSSION 1

Elinor G. Adensan. Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Technical Specification changes Oate of Issuance: October 27, 1981 X'y 4&

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r ATTACHMENT TO LICENSE AMENDMENT NO. 7

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FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided,to maintain document completeness.

Overleaf Amended Page Page 3/4 J-17 3/4T-8 J/4 3-26 3/4 3-25 3/4 3-27 3/4 3-28 3/4 3-35 3/4 3-36 J/4 3-51 gg jgg, 3/4 6-30 3/4 6-29 3/4 7-29 3/4.J-30 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-39 3/4 7-40 3/4 7-45

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3/4 '7'46 3/4 7-49 3/4 7-50 3/4 7-52 3/4 7-51 3/4 7-53 3/4 7-54

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,3/4 7-58 3/4 7-57 3'/4 7-61 3/4 7-62 3/4 7-67 3/4 7-68 3/4 7-69 3/4 7-70 3/4 7-72 3/4 7-71 3/4 8-51 3/4 8-52 3/4 11-7

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TABLE 3.3-3 (Continued)

' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION i

i E5

1 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE a

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION e.

Station Blackout

~

Start Turbine-Driven 2/ Bus Pump and Motor-Driven 6-3/ Bus Either Bus 2/ Bus 1, 2, 3 19 Pumps f.

Auxiliary Feedwater Suct'an Pressure-Low 2/ pump 2/ pump 2/ pump 1, 2, 3 23a i

g.

Trip of Main Feedwater Pumps Start Motor-2 1/ pump 1/ pump

1. 2#

13 dd Driven Pumps

}

=

i' 8.

-LOSS OF POWER 5;

a.

Grid Degraded Voltage 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 14*

9.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM-INTERLOCKS t

j a.

Pressurizer Pressure -

3 2

2 1,2,3 20a P-11 g7 T,yg - P-12 b.

4 2

3 3

20b oj' c.

Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2 20c y

Level-P-14 any operating each operating 5

loop loop

==

P 10.

RWST LEVEL w

a.

Automatic (witchover 3

2 2

1,2,3 14*

to Recirculation

if gg TABLE 3.3-4 (Continued) 55 ENGINEERED SAFETY FEATURE ACILATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

~

i C

y

[j FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 8.

LOSS OF POWER a.

Grid Degraded Voltage 3464 i 173 volts with a

> 3200 volts 8.5 1 0.5 second time delay.

9.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure Manual Block of Safety Injet+. ion P-1151955 psig 5 1965 psig b.

Pressurizer Pressure Manual Enable of Steamline Isolation, P-11 3 1955 psig 1 1945 psig o

T,yg jo c.

S$

Affects Steam Dump, P-12

> 553"F 2 551*F d.

St~eam Generator Level Turbine Trip, Feedwater Isolation P-14 (See 5. above) jI 10.

RWST LEVEL a

jf a.

Automatic Switchover to 1 120 inches 1 114 inches g

Rec;rculation O

4

_.A

t TABLE 3.3-5 ENGINEERED SAFETY FEATURBS RESPONSE-TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.

Manual a.

Safety Injection (ECCS)

NotApplicable Feedw'ater Isolation Not Applicable Reactor Trip (SI)

Not Applicable Containment Isolation-Phase "A" Not Applicable Auxiliary Feedwater Pumps Not Applicable Nuclear Service Water System Not Applicable Containment Air Recirculation Fan Not Applicab,le b.

Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Vent and Purge Isolation' Not Applicable Annulus Ventilation System Not Applicable c.

Containment Isolation-Phase "A"

'Not Applicable Containment Vent and Purge Isolation Not Applicable d.

Steam Line Isolation Not Applicable Purge and Exhaust Isolation pot Applicable e.

2.

Containment Pressure-liigh a.

Safety injection (FCCS) 5 27.0(1) b.

Reactor Trip (from SI) i 2. 0

'c.

Feedwater Isolation

< 9.0 d.

Containment Isolation-Phase "A" (4) 18.0(5)/28.0(0) e.

Containment Vent and Purge Isolation Not Applicable f.

Auxiliary Feedwater Pumps Not Applicable g.

Nuclear Service Water System

< 65.0(5)/76.0(6) h.

Component Cooling Water System 65.0(5)/76.0(6) 3.

Pressurizer Pressure-Low a.

Safety Injection (ECCS) 1 27.0(1)/12.0(5) b.

Reactor Trip (from SI)

's 2.0 McGUIRE - UNIT 1 3/4 3-26 1

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c. -

5 TABLE 3.3-5 (Continued)

)

' ENGINEERED-SAFETY FEATURES RESPONSE TIMES i

f I;'

a o

INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECORDS

~

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c.

Feedwater Isolation

< 9.0

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18.0(5)/28:0(6)j /,

s j

d.

Containment Isolation-Phase "A" (4) e.

Containment Vent and Purge Isolation Not Appifcable' f.

Auxiliary Feedwater Pumps

~

Not Applicable g.

Nuclear Service W6ter System

< 76.0II)/65.5(5)'

76.0(1)/65.0(5) h.

Component Cooling Water - System 4.

Negative Steam Line Pressure Rate - High

{-

a.

Steam Line Isolation

$ 9.0

^

/

5.

Steam Line Pressure-Low u

a.

Safety Injection (ECCS)

\\112.0(5)/22$0(6)-

5 b.

Reactor Trip (from SI)

< 2.0 i

r' c

c.

Feedwater Isolation

< 9.0 7'

~'

d.

Containment Isolation-Phase "A" (4)

,18.0(5)/28.0(6) e.

Containment Vent and Purge Isolation Not Applicable i

f.

Auxiliary Feedwater Pumps Not Applicable

< 65.0(5)/76.0(6) 2-g.

Nuclear Service Water System h.

Component Cooling Water System 65.0(5)/76.0{6) i Steam Line Isolation

-< 9.0

.)

~6.

Containment Pressure--High-High-a.

Containment Spray 5 45.0 s

b.

Containment Isolation-Phase "B" Not Applicable e

~

c.

Steam Line Isolation 5 9.0 l

d.

Containment Air Recirculation Fan 5 610.0 4

7.

Steam Generator Water Level--High-High a.

Turbine Trip Not Applicable ~

b.

Feedwater Isolation 5 13.0 McGUIRE - UNIT 1 3/4 3-27

j;-

TABLE 3.3-5 (Continued)

's

.. ENGINEERED SAFETY FEATURES RESPONSE TIMES

. ar -

INITIATINGSIGNdL'ANDFUNCTION RESPONSE TIMES IN SECONDS f

8.

Steam Generator Water Level--Low-Low a.

Motor-driven Auxiliary 1 60.0 Feedwater Pumps b.

Turbine-driven Auxiliary 1 60.0 Feedwater Pump 9.

Station Blackout a.

Turbine-driven Auxili: fry,'

5 60.0 Feedwater Pump

/

b.

Motor-driven Auxiliary 5 60.0 Feedwater Pumps j

~~'

10.

RWST Level

~

Automatic,Switchover to Recirculation 5 60.0 a.

. 11.

Trip of. Main Feedwater Pumps

~

Moto'r.-drisen. Auxilia'ry Feedwater Pumps 1 60.0 a.

Note:

Response':ti;te for Motor-driven 5 60.0 Auxj,1liary feedwater Pumps on all S.I. signal starts n

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• s McGUIRE - UNIT--I 3/4 3-28 Amendment No. 7 9

y y

y 9

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INSTRUMENTATION

~

3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 9*

1 y;

~

\\ 3.3.3.J The radiation' monitoring instrumentation channels shown in Table

'3.3-6 shall be OPERABLE with~their alarm / trip setpoints within the specified s

limits.

APPLICABILITY:

AsshiwntinTable3.3-6.

'.V' ACTION:

With a radiation monitoring channel alarm / trip setpoin' exceeding a.

the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

~

b.

With one or more radiation monitoring ~ channels inoperable, take the ACTION shown in Table 3.3-6.

~

The provisions of Specifications 3.0.3.and 3.0.4 are not applicable.

c.

~,

. 7

_l.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radistion monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown.in Table 4.3-13.

~

?s McGdIRE - UNIT 1 3/4 3-35 e

4 k

. TABLE 3.3-6 if 8

RADIATIO" MONITORING INSTRUMENTATION E

MINIMUM E

INSTRUMENT CHANNELS APPLICABLE ALARM / TRIP

' MEASUREMENT OPERABLE MODES SETPOINT RANGE ACTIOM M

1.

AREA MONITGRS a.

Fuel Storage Poo1 Area

_y 4

Criticality Monitor 1-(Fuel Bridge)

-< 15 mR/hr 10

- 10 mR/hr 24 0

8 ad/hr 28

b. Containment Area 2

1, 2, 3, & 4 N/A 10 - 10 r

2.

PROCESS MONITORS a.

Fuel Storage Pool Area Gaseous Activity -

Ventilation System 7

Isolation 1

1 2 x background 10 - 10 cpm 26 R

b.

Control Room Outside Air Intake, Gaseous Activity-y Ventilation System 7

g Isolation 2

ALL MODES 1 2 x background 10 - 10 cpm 27 c.

Containment i.

Gaseous Activity 1

(Low-Range) 8 7

a)RCS Leakage Detection 1, 2, 3, & 4 N/A 10 - 10 cpm 25 ii.

Particulate Activity 1

(Low Rar.ge) 7 a)RCS Leakage Detection 1, 2, 3, & 4 N/A 10 - 10 cpm 25 k

d.

Noble Gas Effluent Monitors 0

8 g

1.

Unit Vent 1

1, 2, 3, & 4 N/A 10 - 10 rad /hr 28 g

(gamma) s

[

" With fuel in the storage pool or building P

With irradiated fuel in the storage pool u

\\

v TABLE 4.3-7

?j ACCIDENT-MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

m CHANNEL CHANNEL g

mSTRUMENT CHECK CALIBRATION n.

w Containment Pressure M

R 2.

Reactor Coolant Temperature - T and TCOLD (Wide Range)

M R

~

liOT 3.

Reactor Coolant Pressure - Wide Range -

M R

4.

Pressurizer Water Level M

R 5.

Steam Line Pressure M

R R

6.

Steam Generator Water Level - Narrow Range M

R y

7.

RWST Water Level M

R Y

8.

/.uxiliary Feedwater Flow Rate M

R 9.

Reactor Coolant System Subcooling Margin Monitor M

R 10.

PORV Position Indicator M

R 11.

PORV Block Valve Position udicator M

R 12.

Safety Valve Position Indicator M

R 13.

In-Core Thermocouples M

R 14.

Containment Water Level (Wide Range)

M R

-i_

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detec-

' tion zone shown in Table ~3.3-11 shall be OPERABLE.

APPLICABILITY:

Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-11:

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) a.

with the inoperable instrument (s) at least once per heur, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

~

b.

Rastore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

The provisions of' Specifications 3.0.3 and 3.0.4 are not applicable.

c.

' SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above required smoke detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fira detectors'which are not accessible during plant opera-tidn shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous six months.

Each of the above required fixed temperature / rata of rise detection instruments shall be demonstrated OPERABLE as follows:

For nonrestorable spot-type detectors, at least two detectors a.

out of every hundred, or fraction thereof, shall be removed every five years and sent to a nationally recognized testing laboratory for tests.

For each failure that occurs on the de-tectors removed, two additional detectors'shall be removed and tested.

McGUIRE - UNIT 1 3/4 3-52 Amendment No. 7

SURVEILLANCE REQUIREMENTS (Continued) b.

For restorable spot-type heat detectors, at least one detector on each signal initiatinr, circuit shall be demonstrated OPERABLE at least once per 6 e.anths by performance of a CHANNEL FUNCTIONAL TEST.

Different detectors shall be selected for each test.

Fire detectcrs which are not accessible during plant operation shall be demonstrated OPERABLE by the perfor-mance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> urless performed in the previous six months.

4.3.3.7.2 The NFPA Code 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.7.3 The non-suparvised circuits betteen the local panels in Specification 4.3.3.7.2 and the control room shall be den.onstrated OPERABLE at least once per 31 days.

McGUIRE - UNIT 1 3/4 3-52a Amendment t'o. 7

t CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen monitors shall be OPERABLE.

APPLICABILITY:.$0 DES 1and2.

ACTION:

With one hydrogen monitor inoperable, restore the inoperable monitor to.

OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

~~

SURVEILLANCE REQUIREMENTS 4.6.4.1-Each hydrogen monitor shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31-days, and at least once per,92 days on a STAGGERED TEST BASIS

'by performing a CHANNEL CALIBRATION asing hydrogen gas mixtures to obtain-

, calibration points of:

a Zero volume percent hydrogen.

b.

Nine volume percent hydrogen.

i 4

McGUIRE - UNIT 1 3/4 6-29 Amendment No. 7 L

CONTAINMENT SYSTEMS ELECTRIC HYOROGEN RECOMBINERS - W LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying during a recombiner system i

functional test that the minimum heater sheath temperature increases to greater than or equal to 700 F within 90 minutes.

Upon reaching 700 F, increas.e the power setting to' maximum for 2 minutes and verify that the power meter reads greater than or equal to 60 kw.

b.

At least once per 18 months by:

1.

Performing a CHANNEL CALIBRATION of all recombiner instrumenta-tion and control circuits, 2.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure (i.e.,

loose wiring or structural connections, deposits of foreign materials, etc.), and 3.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test.

The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

McGUIRE - UNIT 1 3/4 6-30

dmg l(

TABLE 3.7-4a

~

C j{

SAFETY RELATED HYDRAULIC SNUBBERS *~

- E HIGH RADIATION l

s' ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT ra PIPE SUPPORT T_YPE/QUAN.

LOCATION INACCESSIBLE SHUTDOWN **..

TO REMOVE 1-MCA-FW-H121 ISNB.H HH53 EL713-03 I

N.

N 1-MCA-FW-H122 ISNB.H HH53 EL697-Oo I

N N

1-MCA-FW-H123 ISNB.H HH54 EL697-06 I

N N

1-MCA-FW-H125 ISNB.H HH56 EL697-06 I

N N

1-MCA-FW-H126 ISNB.H JJ50 EL762-04 A

N N

1-MCA-FW-H134 2SNB.H KK53 EL728-04 I

N N

1-MCA-FW-H136 ISNB.H KK52 EL759-00 A

N N

1-MCA-FW-H148 ISNB.H KK53 EL736-00 I

N N

1-MCA-FW-H149 ISNB.H KK53 EL736-06 I

N N

Ri 1-MCA-FW-H160 2SNF.H JJ50 EL759-11 I

Y N

1-MCA-FW-H162 ISNJ.H JJ50 EL758-01 I,

Y N

Y 1-MCA-KC-H457 3SNB.H HH55 EL733-00 A'

N N

Q!

1-MCA-KC-H458 3SNB.H HH56 EL733-00 A

N N

1-MCA-KC-H459 3SNB.H HH57 EL733-00 A

N N

.1-MCA-KC-H460 3SNB.H HH57 EL733-00

.A N

N 1-MCA-KC-1066 ISNB.H HH55 EL757-08

,A N

-N 1-MCA-KC-1068 ISNB.H JJ58 EL755-10 SA N

N 1-MCA-KC-1076 ISNB.H HH54 EL747-09 A

N N

i 1-MCA-KC-1097 ISNB.H GG57 EL742-00 A

N N

1-MCA-KC-1102 ISNB.H KK56 EL717-11 I

N N

1-MCA-KC-1106 ISNB.H HH56 EL757-05 A

N N

1-MCA-KC-1110 ISNB.H KK55 EL760-10 A

N N

4 1-MCA-KC-1313 ISNB.H MM52 EL760-10 A

N N

1-MCA-KC-2137 ISNB.H GG57 EL740-07 A

N N

1-MCA-KO-0052 ISNB.H AA42 EL747-09 A

N-N c:

2 4

mam

~-

hh TABLE 3.7-4a s

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SAFETY RELATED HYDRAULIC SNUBBERS

• C 55 HIGH RADIATION ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **_

TO REMOVE e

1-MCA-KD-0062 ISNB.H 8842 EL747-09 A

N N

1-MCA-KD-0074 ISNB.H AA41 EL740-00 A

N N

1-MCA-KD-0083 ISNB.H AA42 EL743-07 A

N N

1-MCA-KD-0084 ISNB.H AA42 EL741-07 A

N N

1-MCA-KD-0095 ISNB.H AA41 EL737-04 A

N N

1-MCA-KD-0099 ISNB.H AA42 EL744-10 A

N N

1-MCA-KD-0104 ISNB.H BB41 EL739-10 A

N N

1-MCA-KD-0113-ISNB.H B842 EL743-07 A

N N

1-MCA-KD-0114 ISNB.H BB42 EL741-08 A

N N

1-MCA-KD-0125 ISNB.H BB41 EL737-04 A

N N

1-MCA-KD-0128 ISNB.H BB41 EL744-10 A

N N

u,

];

1-MCA-KD-0163 ISNB.H AA42 EL743-07 A

N N

1-MCA-KD-0173 ISNB.H B842 EL743-07 A

N N

sa L,

1-MCA-KF-H451 ISNB.H LL51 EL756-00 A

N N

c) 1-MCA-KF-2093 ISNB.H PPS1 EL759-03 A

N N

1-MCA-KF-2097 ISNB.H PP52 EL760-09 A

N N

1-MCA-4R-1021 2SNB.H LL55 EL776-00 I A N

N 1-MCA-KR-2079 1TNB.H EE54 EL732-03 A

N N

1-MCA-LD-0053 ISNB.H AA42 EL734-08.

A N

N 1-MCA-LD-0063 ISNB.H BB42 EL734-09 A

N N

1-MCA-LD-0077 ISNB.H AA43 EL737-03 A

N N

1-MCA-LD-0078 ISNB.H AA43 EL737-11 A

N N

1-MCA-LD-0087 ISNB.H AA43 EL744-12 A

N N

gr 1-MCA-LD-0107 ISNB.H B843 EL737-00 A

N N

g 1-MCA-LD-0108 ISNB.H 8843 EL737-11 A

N N

g 1-MCA-LD-0112 ISNB.H 8843 EL742-12 A

N N

g 1-NCA-NB-H484 ISNB.H NN51 EL742-03 A

N N

n O.

-%s-s.

k

~ TABLE 3.7-4a c

j[

SAF'ETY RELATED HYDRAULIC SNUBBERS'*

C Ei HIGH RADIATION '

~7 ACCESSIBLE /

ZONE DURING ESPECIAL'LY DIFFICULT s

PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **-

TO REMOVE 1-MCA-NS-H486 ISNB.H NN51 EL742-03 A

N

'N 1-MCA-N8-H491 ISNB.H NN51 EL742-03 A

N-N 1-MCA-N8-H493 ISNB.H NN51.EL742-03 A

N N

1-MCA-NB-1015 2SNB. H NN56 EL742-06 I

N.

N-1-MCA-N8-1033 ISNB.H PP56 EL737-08 I

N

.N 1-MCA-NB-1038 ISNB.H PP56 EL742-06 I

Y N

1-MCA-N8-1102 ISNB.H NN59 EL729-00 A

N N

1-MCA-N8-1196 ISNB.H NN56 EL720-00 I

N N

1-MCA-NB-1224 ISNB.H NN56 EL719-06 I

N N

ti 1-MCA-NS-1244

.1SNB.H NN53 EL744-03 I

Y.

N 1-MCA-N8-1372 ISNB.H MM51~EL740-03 I-N N

T 1-MCA-NB-1505 ISNB.H

.PP59 EL726-09 I

N-N O

1-MCA-NB-1506

.~

2SNB.H NN57 EL'?6-09 I

N N

1-MCA-NB-1509 ISNB..

PP61 EL72 ~ 09 I'

N N

--1SNB[H 1-MCA-NO-1539 H

NN57.EL717-01 I

N N

1-Mr4 N3-1542 ISNB.H PP57 EL717-01

I N.

N 1-MCA-N8-1560 1SNB.H NN57 EL744-06 A

N

-N 1-MCA-NB-1565 ISNB.H QQ59 EL721-09 I

N-N 1-MCA-NS-1566 ISN8.H QQ59 EL721-05 I

N.

N 1-MCA-NB-1589 ISNB.H

-QQ56 EL726-00 I

N N.

1-MCA-NB-2132 ISNB. H NN56 EL743-06 I

N N

1-MCA-N8-2/06 ISNB. H NN51 EL731-01 I

Y' N

1-MCA-N8-23-Q ISNB.H NN53 EL744-00' I

N

-N 1-MCA-NB-2313 ISNB.H NN53 EL744-00 I

N N.

1-MCA-NB-2317 ISNB.H

.NN55 EL744-00 I

N.

N MCA-NB-2383 2SNB.H PPS6 EL745-06 I

N N

c, c:

1-MCA-NB-2384 ISNB.H PPS6 EL745-06 I

N N

1-MCA-N8-2389

-2SNB.H PP56 EL7.39-04 I

N N

.iB 1

l i

4

,e

xy, TABLE 3.7-4a Sj SAFETY RELATED HYi)RAULIC SNUBBERS

• C

' E5 HIGH RADIATION

-4 ACCESSIBLE /

ZONE DURING-ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE

1. -1-NCA-NB-2391 ISNB.H PPS6 EL742-06 I

Y

.N 1-MCA-NC-H053 ISNB.H DD52 EL737-03 I

Y N

1-F 'A-NC-H056 ISNB.H FF52 EL744-06 I

Y N

1-MCA-NC-H068 ISNB.H HH53 EL710-06 I

Y N

1-MCA-NC-H070 ISNB.H GG53 EL724-00 I

Y N

1-MCA-NC-H074 ISNB.H EE53 EL725-08 I

Y N

1-MCA-ND-H175 ISNB.H HH53 EL726-07 I

Y N

1-MCA-ND-H178 ISNB.H HH53 EL726-09 I

Y N

1-MCA-ND-H179 ISNB.H HH53 EL735-02 I

Y N

1-MCA-ND-H181 ISNB.H HH52 EL733-03 I

Y N

1-MCA-ND-H246 2SNB.H GG53 EL696-09 A

N N

If 1-MCA-ND-H247 ISNB. H GG53 EL696-09 A'

N N

1-MCA-ND-H248 ISNB.H GG53 EL696-09 A

N N

I' 1-MCA-ND-H249 ISNB.H FF53 EL696-09 A

N N

k$

l-MCA-ND-H250 ISNB.H GG53 EL708-00 A

N N

1-MCA-ND-H252 ISNB.H HH53 EL706-00 I

Y N

1-MCA-ND-H253 ISNB.H HH53 EL706-00 II Y

N 1-MCA-ND-H254 2SNB.H HH53 EL708-00 I

Y N

1-MCA-ND-H255 2SNB.H HH54 EL708-00 I

Y N

1-MCA-ND-H256 ISNB.H HH54 EL706-00 I

Y N

1-MCA-ND-H257 2SNB.H HH55 EL708-00 I

Y N

s 1-MCA-ND-H258 ISNB.H GG53 EL726-00 I

Y N

. ((

1-NCA-ND-H270 ISNB. H MM52 EL755-09 I

N N

a 1-MCA-ND-H271 ISNB.H LL52 EL757-09 I

N N

1-MCA-ND-H272 ISNB.H HH52 EL734-03 I

Y N

((

1-MCA-ND-H273 ISNB.H JJ51 EL744-00 I

Y N

1. -Exempted from periodic functional testing.

i q

W f

TABLE 3.7-4a

~

~

SAFETY RELATED HYDRAULIC SNUBBERS

• Ei HIGH RADIATION

?

ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT w

PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN ** ~

TO REMOVE 1-MCA-ND-H274 2SNB.H JJ52 EL742-06 I

Y N

1-MCA-ND-H275 ISNB.H HH52 EL741-00 I

Y N

1-MCA-ND-H277 ISNB.H HHb2 EL741-00 I

Y N

1-MCA-ND-H281 2SNB.H KK52 EL743-08 I

Y N

1-MCA-ND-H28%

ISNB.H KK52 EL738-03 I

N N

1-MCA-ND-H286 ISNB.H LL51 EL744-00 I

N N

1-MCA-N6 - H287 ISNB.H LL51 EL744-00 I

N N

1-MCA-ND-H289 ISNB.H LL51 EL739-00 I

N 1-MCA-ND-H290 ISNB.H LL52 EL742-06 I

N

'N Ri 1-MCA-ND-h296 ISNB.H MM52 EL735-06 I

N N

1-MCA-ND-H297 ISNB.H MM52 EL742-06 I'

N N

l' 1-MCA-ND-H298 ISNB.H MMS 2 EL744-06 I

N N

O 1-MCA-ND-H301 ISNB.H HH53 EL715-11 I !

Y N

1-MCA-ND-H304 ISNB.H HH53 EL728-07 I

Y N

1-MCA-ND-H315 ISNB.H KK51 EL744-10 I

N N

1-MCA-ND-H321 ISNB.H HH53 EL747-07 II N

N 1-MCA-NI-H009 ISNB.H HH53 EL723-07 I

Y N

1-MCA-NI-H010 ISNB.H HH53 EL719-00 I

Y N

~

1-MCA-NI-H012 1SNB. H GG53 EL724-06 I

Y N

1-MCA-NI-H083 JANB.H JJ53 EL724-06 I

Y N

1-MCA-NI-H249 ISNB.H JJ53 EL725-03 I

Y N

1-MCA-NI-H253 2SNB.H HH53 EL724-06 I

Y N

1-MCA-NI-H255 ISNB.H HH53 EL724-06 I

Y N

1-MCA-NI-H286 ISNB.H JJS1 EL742-06 I

Y N

$5 1-MCA-NI-H315 ISNB.H HH52 EL761-00 A

N N

1-MCA-NI-H352 ISNB.H JJ54 EL728-00 I

N N

N a

W gg TABLE 3.7-4a

.~

8 SAFETY RELATED HYDRAULIC SNUBBERS *

)C-

-d HIGH RADIATION ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE

~

1. -1-MCA-NI-H355 2SNB.P FF53 EL716-00 I

Y N

1-MCA-NS-H052 ISNB.H JJ51 EL742-06 I

Y N

1-MCA-NS-H053 ISNB.H JJ52 EL744-00 I

Y-N 1-MCA-NS-H060 ISNB.H JJ51 EL762-06 A

Y N

1-MCA-NS-H061 ISNB.H JJ51 EL759-09 I

Y N

1-MCA-NS-H073 2SNB.H JJ52 EL757-06 I

Y H

1-MCA-NS-H085 2SNB. H HH54 Ei.699-00 I

Y N

1-MCA-NS-H088 l a.u. H JJ53 EL722-00 I

Y N

1-MCA-NS-H091 2SNB.H KK52 EL734-06 I

Y N

1-MCA-NS-H098 2SNB.H HH53 EL716-06 I

Y N

1-MCA-NS-H101 ISNB.H HH52 EL734-00 I

Y N

u,

]s 1-MCA-NS-H102 ISNB.H HH53 EL728-03 I'

Y N

1-MCA-NS-H105 2SNB.H GG54 EL704-02 I

t, N

L, 1-MCA-NS-H106 2SNB.H GG56 EL704-03 A!

N N

1-MCA-NV-H303 ISNB.H JJL3 EL724-06 I

Y N

1-MCA-NV-H306 ISNB.H KK55 EL724-00 I

N N

1-MCA-NV-H374 2SNB.H GG52 EL745-06

I Y

N 1-MCA-HV-H396 ISNB.H GG52 EL745-06 I

Y N

1-MCA-NV-H433 ISNB.H JJ52 EL728-00 I

Y N

1-MCA-NV-H435 ISNB.H HH52 EL724-00 I

Y N

1-MCA-NV-H450 ISNB.H JJ55 EL726-00 I

N N

2m g

1-MCA-NV-H457 ISNB.H JJ56 EL724-00 I

N N

a 1-MCA-NV-H464 ISNB.H JJ54 EL726-00 I

N N

g 1-MCA-NV-H467 ISNB.H HH52 EL724-00 I

Y N

g 1-MCA-NV-H471 ISNB.H JJ55 EL726-00 I

N N

5

1. -Exempted from periodic functional testing.

1 J

s h[

TABLE 3.7-4a C

j{

SAFETY RELATED HYDRAULIC SNef9ERS*

i i

EE HIGH RADIATION ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE 1-MCR-BB-0663 ISNB.H D 354 40-09 745-11 I

Y

' N 1-MCR-BB-0665 ISNB.H 0 354 40-09 745-11 I

Y N

j 1-MCR-88-0666 ISNB.H D 354 40-09 744-11 I

Y N

j 1-MCR-88-0701 ISNB.H C 201 30-10 745-03 I

Y N

1-MCR-BB-0709 ISNB.H C 201 30-10 745-08 I

Y N

1-MCR-BB-0710 ISNB.H C 201 30-10 748-08 I

Y N

1-MCR-BB-0713 ISNB.H C 201 30-10 748-08 I

Y N

1-MCR-BB-0714 ISNB.H C 201 30-10 748-08 I

Y N

1-MCR-CA-H382 ISNB.H B 156 22-05 773-08 I

Y.

N 1-MCR-CA-H388 ISNB.H C 190 40-06 766-10 I

Y N

1-MCR-CA-H389 1SNB.H C 182 40-02 766-11 I

Y N

l dd 1-MCR-CA-H391 ISNB.H C 251 21-08 773-08 I'

N N

1-MCR-CA-H394 ISNB.H C 180 32-00 769-06 I

Y N

l' 1-MCR-CA-H396 ISNB.H B 113 22-05 773-08 I'

N N

hs 1-MCR-CA-H443 ISNB.H D 359 40-02 766-09 I

Y N

1-MCR-CA-H445 ISNB.H A 001 31-06 769-08 I

Y N

1-MCR-CA-H447 ISNB.H D 289 21-08 773-06

?I Y

N 1-MCR-CA-H487 ISNB.H A 002 29-09 769-07 I

Y N

1-MCR-CA-H490 ISNB.H-A 024 22-05 773-06 I

Y N

1-MCR-CF-H159 2SNB.H D 339 40-04 745-08 I

Y N-1-MCR-CF-H160 ISNB.H D 340 40-05 753-00 I

Y N

1-MCR-CF-H189 ISNB.H 0 340 40-09 753-03 I

Y N

1-MCR-CF-H210 ISNB.H C 249 40-03 753-00 I

Y N

1-MCR-CF-H302 2SNB.H C 249 40-03 745-08 I

Y N

1-MCR-KC-0538 ISNB.H B 105'47-01.733-07 A

N N

1-MCR-KC-0539 ISNB.H B 111 49-02 720-00 I

Y N

i 1-MCR-KC-0543 ISNB.H A 054 50-09 729-00 A

N.

N l

1-MCR-KC-0544 ISNB.H A 059 50-06 729-00 A

N N

1-MCR-KC-0546 ISNB.H A 069 48-00 729-01 A-N N

i 4

4

+

,4-

+

L. -

-. m

~ i

f(

TABLE 3.7-4a

~

~

S g;

SAFETY RELATED HYDRAULIC SNUBBERS

• 4

~

E!

HIGH RADIATION

-4 ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE 1-MCR-KC-0573 ISNB.H A 066 51-08 727-06 I

Y N

1-MCR-KC-0574 ISNB.H A 055 53-06 728-06 I

Y N

1-MCR-KC-0580 ISNB.H C 247 53-06 727-06 I

Y N

1-MCR-KC-0661 ISNB.H A 062 38-04 741-03 I

Y N

1-MCR-KC-0818 ISNB.H A 062 38-04 741-00 Y

N 1-MCR-KC-0827 ISNB.H B 134 38-00 740-10 Y

N 1-MCR-KC-0828 ISNB.H B 134 38-00 741-01 I

Y N

1 1-MCR-KC-0870 ISNB.H D 304 29-00 733-08 I

Y N

1-NCR-KC-0871 ISNB.H D 304 29-00 733-10 I

Y N

1-MCR-KC-0880 ISNB.H D 308 53-03 729-03 I

Y N

1. -1-MCR-NC-SG-A

.2SNB.H A 022 31-05 777-08 I

Y N

If

1. -1-MCR-NC-SG-B 2SNB.H B 158 31-05 777-08 I

Y N

1. -1-MCR-NC-SG-C 2SNB.H C 202 31-05 777-08 I

Y N

ld

1. -1-MCR-NC-SG-D 2SNB.H D 338 31-05 777-08 I

Y N

1-MCR-NC-0502 ISNB.H B 116 37-08 746-09 I

Y N

1-MCR-NC-0546 ISNB.H B 096 36-11 759-08 I

Y N

l.-MCR-NC-0549 ISNB.H 8 105 32-00 749-00.

I Y

N 1-MCR-NC-0551 ISNB.H A 066 25-10 737-00 I

Y N

1-MCR-NC-0554 ISNB.H A 076 24-03 743-00 I

Y N

1-MCR-NC-0557 ISNB.H B 090 25-09 743-00 I

Y N

1-MCR-NC-0559 ISNB.H B 104 24-03 743-00 I

Y N

2T 1-MCR-NC-0561 ISNB.H B 104 24-03 743-00 I

Y

.N 1

1-NCR-NC-0562 ISNB.H B 111 25-06 738-00 I

Y N

EF 1-MCR-NC-0564 ISNB.H B 114 25-10 737-00 I

Y N

1-NCR-NC-0565 ISNB.H B 096 34-11 750-00 I

Y N

1-NCR-NC-0570 ISNB.H A 054 32-07 727-08 1

Y N

d*

1. -Exempted from periodic functional testing.

TABLE 3.7-4a

~

~

5 A

SAFETY RELATED HYDRAULIC SNUBBERS *

~

k HIGH RADIATION 9

ACCESSIBLE /

ZONE'DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE 1-MCR-NV-0718 ISNB.H B 108 56-00 734-00 I

Y N

1-MCR-NV-0729 ISNB.H C 225 40-02 735-00 I

Y N

1-MCR-NV-0734 1SNB.H C 230 46-00~731-00 I

Y N'

1-MCR-NV-0735 ISNB.H C 230 46-00 730-09 I

Y

.N 1-MCR-NV-0738 ISNB.H C 229 52-06 731-00

'I Y

N 1-MCR-NV-0741 ISNB.H C 220 52-06 731-00 I

Y

'N.

1-MCR-NV-0746 ISNB.H C 221 47-03 734-00 I

Y N

1-MCR-NV-0747 ISNB.H C 211 53-11-730-06 I

Y N.

1-MCR-NV-0758 ISNB.H B 113 52-06 730-08 I

Y N

1-MCR-NV-0760 ISNB.H B 112.56-00 732-10 I

Y.

N 1-MCR-NV-0761 ISNB.H B 112 56-00 733-03 I

Y N.

4 1-MCR-NV-0763

-ISNB.H B 110 53-06 735 I' Y

N 1-MCR-NV-0766 ISNB.H B 109 53-05 738-08 I

Y N

?

1-MCR-NV-0791 ISNB.H C 235 39-08 738-03 Il Y

N S

1-MCR-NV-0792 ISNB. H C 235 39-08 737-11 I'

Y N

1-MCR-NV-0805 ISNB.H D 313 39-02 745-01 I

Y N

1-MCR-NV-0807 ISNB.H D 316.38.-04 741-10.

I Y

N 1-MCR-NV-0808 ISNB.H D 316 38-04 742-03 I

Y

.N 1-MCR-NV-0831 ISNB.H B 144'40'-09 742-00 I

'Y

.N 1-MCR-NV-0840 ISNB.Il A 057 39-10 745-01 I~

Y N

g 1-MCR-NV-0851 ISNB.H A 038 39-04 737-10 I -

Y N-

• ~

m 1-MCR-NV-0852 1SNB.H A 032 39-04 738-02 I

-Y N

'h 1-MCR-NV-0855 ISNB.H A 043 38-04 735-03 I

Y-N o

1-MCR-NV-0931 1SNB.H D 312 30-00 746-00 I

Y. -

N A

1-MCR-NV-0949 ISNB.H B 132 39-10 739 I Y

N

==

1-MCR-NV-0" 1SNB.H A 065 33-40 245-02 I

Y N.

1-MCR-NV-0953 ISNB.H B 133 37-08 744-06 I

Y N

u l-MCR-NV-0954 ISNB.H B 134 32-08 744-06 I

Y

.N 1-MCR-NV-0956 ISNB.H B 129 32-00 745-02 I

_Y N-1-MCR-NV-0963 ISNB.H C 243 41-06 737-00 I

'Y N-L

e 73 TABLE 3.7-4a

AFElY RELATED HYDRAULIC SNUBBERS

• E!

HIGH RADIATION El ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /00AN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE a

1-MCR-NV-0966 ISNB.H C 237 36-06 744-06 I

Y N

1-MCR-NV-0967 ISNB.H C 240 33-03 745-02 I

Y N

1-MCR-NV-0969 ISNB.H C 239 32-00 744-11 I

Y N

1-MCR-HV-0970 ISNB.H C 236 33-00 746-02 I

Y N

1-MCR-NV-0972 ISNB. H C 239 30-03 745-02 I

Y N

1-MCR-NV-1005 ISNB.H B 108 45-12 734-00 I

Y N

1-MCR-NV-1006 2SNB.H B 108 45-03 734-00 I

Y N

1-MCR-NV-1007 ISNB.H B 108 34-09 734-08 I

Y N

1-MCR-NV-1011 ISNB.H A 072 34-08 738-06 I

Y N

1-MCR-40-1014 ISNB.H B 105 48-08 735-03 I

Y N

1-MCR-NV-1031

.1SNB.H A 016 50-06 734-00 I

Y N

2d 1-MCR-NV-1032 ISNB.H A 016 46-06 734-00 I'

Y N

1-MCR-NV-1034 ISNB.H A 015 51-06 734-00 I

Y N

7' 1-MCR-NV-1043 ISNB.H D 303 52-06 731-00 I:

Y N

1-MCR-NV-1047 ISNB.H D 299 50-09 734-00 I

Y N

1-MCR-NV-1048 ISNB.H 0 299 45-06 733-00 I

Y N

1-MCR-NV-1051 ISNB.H D 301 39-06 737-07

I Y

N 1-MCR-HV-1052 ISNB.H 0 301 40-00 735-00 I

Y N

'-MCR-NV-1060 ISNB.H B 112 34'-05 737-03 I

Y N

1-MCR-NV-1064 ISNB.H B 100.33-06 738-06 I

Y N

~

x MCR-NV-1057 ISNB.H B 112 34-04 737-00 I

Y N

ff l'"CR-NV-1070 ISNB. H D 299 52-10 710-08 I

Y-N l-M R-NV-1071 ISNB.H A 016 53-06 730-03 I

Y N

St 1-MCR-NV-1147 ISNB.H C 191 45-06 755-00 I

Y N

1-MCR-NV-1201 ISNB.H B 124 52-00 734-01 I

Y N

1-MCR-NV-1206 ISNB.H B 124 55-06 730-03 I

Y N

if

'l-MCR-NV-1213 1SNB.H B 136 47-02 731-07 I

Y N

1-MCR-NV-1214 ISNB.H B 136 48-11 731-07 I-Y N

1-MCR-NV-1227 ISNB.H C 211 57-02 731-05 I

Y N

1-MCR-NV-1232 ISNB.H C 230 54-09 730-03 I

Y N

~

i-

{

TABLE 3.7-4a C

E N

SAFETY RELATED HYDRAULIC SNUBBERS

• n, i

g:

HIGH RADIATION

?7 ACCESSIBLE /

ZONE DURING ESPECIALLY DIFcil: ULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN ** -

TO REMOVE 1-MCR-SM-H006 ISNB.H A 009 38-03 782-01 I

N N

'-MCR-SM-H083 ISNB.H B 096 38-00 738-02 I

Y h

1-MCR-SM-H084 ISNB.H C 185 38-00-782-04 I

N N

1-MCR-SM-H086 ISNB.H C 185 37-11 803-01 I

N N

1-MCR-SM-H087 ISNB.H C 186 37-11 804-06 I

N N

1-MCR-SM-H090 ISNB.H D 354 37-11 801-03 I

N N

1-MCR-SM-H091 ISNB.H D 354 37-11 802-01 I

N N

1-MCR-SM-H093 ISNB.H D 354 38-00 785-05 I

N N~

1-MCR-SM-H094 ISNB.H D 354 38-00 784-08 I

N N

ti 1-MCR-SM-H158 1SNB.H B 171 38-03 783-02 I

N N

1-MCR-SM-H159 ISNB.H B 171 38-03 782-04 I.

N N

T 1-MCR-SM-H161 ISNB.H B 171 38-02 803-01 I

N N-1-MCR-SM-H162 ISNB.H B 171 38-02 804-02 I

N N

1-MCR-VQ-0506 ISNB.H C 260 58-11 755-00_

I N

N 1-MCR-VQ-0508 ISNB.H C 262 60-05 755-00 I

N N

1-MCR-VQ-0514 ISNB.H C 262 61-08 809-09 I

N N

1-MCR-WL-H996 ISNB.H B 116 56-00 731-06 I

N N

1-MCS-AS-H237 ISNB.H

-U32 EL747-00 I

N N

1-MCT-CF-H101 ISNB.H IH34 EL763-00 A

N N

1-MCT-CF-H103 ISNB.H IJ34 EL763-00 A

N N

1-MCT-CF-H105 ISNB.H IJ34 EL762-05 A

N N

1-MCT-CF-H107 ISNB.H IJ34 EL763-00 A

N N

1-MCT-CF-H219 ISNB.H IH32 EL751-06 A

N N

1-MCT-CF-H224 ISNB.H IJ34 EL754-06 A

N N

1-MCT-CF-H232 ISNB.H IJ34 EL751-06 A

N N

E:

1-MCT-CF-H233 ISNB.H IG34 EL751-06 A

N N

2 1-MCT-CF-H236 ISNB.H IF32 EL747-07 A

N N

1-MCT-CF-H240 2SNB.H IG31 EL743-06 A

N N

if TABLE 3.7-4a fj pg SAFETY RELATED HYDRAULIC SNUBBERS

• a i

HIGH RADIATION

-4 ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPESUPPCg]

TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE 1-Mi." CF-H2'?

2SNB.H IG30 EL743-06 A

N

,N 1-MCl-CF-H24/

ISNB.H IF31 EL751-09 A

N N

1-MC f-LF-H255 ISNB.H IG32 EL753-00 A

N N

1-MC5 '.' H257 ISNB.H IG32 EL753-06 A

N N

1-mci-CF-H260 ISNB.H IG32 EL755-06 A

N N

1-MCT-SM-H041 2SNB.H 1833 EL764-06 A

N N

1-MCT-SM-H043 ISNB.H IC33 EL764-03 A

N N

1-MCT-SM-H051 ISNB.H IG34 EL774-08 A

N N

1-MCT-SM-H053 ISNB.H IH34 EL774-08 A

N N

1-MCT-SM-HC54 ISNB.H IH34 EL774-08 A

N N

1-MCT-SM-H121 2SNB.H IF33 EL742-10 A

N N

dd 1-MCT-SM-H123 2SNB.H IE33 EL742-09 A'

N N

1-MCT-SM-H176 2SNB.H IF33 EL742-09 A

N N

l' 1-HCT-SM-H177 2SNB.H IE33 EL742-09 A

N N

E?

1-MCY-FW-H139 2SNB.H KK49 EL757-09 A

N N

i 2-MCA-NB-H089 ISNB.H QQ57 EL723-00 I

N N

2-MCA-NB-H013 ISNB.H QQ60 EL721-05 iA N

N 2-MCA-NB-H014 ISNB.H QQ60 EL721-09 A

N N

• Saubbers may added to safety related systems without prior License Amendment to Table 3.7-4a jI provided that a revision to Table 3.7-4a is included with the'next License Amendment request.

s 4

Et

• • Modifications to this column due to changes in high radiation areas may be made without prior i

E License Amendment provided that a revision to Table 3.7-4a is included with the next License

{

Amendment request.

N

~

' TABLE 3.7-4b E

g SAFETY RELATED MECHANICAL SNUBBERS

• E HIGH RADIATION y

ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE MC-1683-KC.15-R013 ISNB.M KK53 EL743-08 A

N N

MC-1683-KC.21-R008A ISNB.M KK58 EL769-04 A

N

.N MC-1683-KC.39-R085 2SNB.M MM58 EL725-10 A

N N

MC-1683-KC.39-R086 2SNB.M MM58 EL725-10 A

N N

MC-1683-KC.48-R013 ISNB.M JJ55 EL761-11 A

N N

MC-1683-KC.59-R007 2SNB.M KK56 EL757-10 A

N N

MC-1683-NB.01-R025 ISNB.M PP59 EL745-06 I'

N N

MC-1683-NB.05-R076A ISNB.M MM58 EL723-00 A

N N

MC-1683-NB.09-R003A ISNB.M NN56 EL743-11 I

N N

MC-1683-NB.14-R002A ISNB.M MM58 EL717-02 A

N N

MC-1683-NB.19-R014 2SNB.M PP56 EL726-04 A

N N

R MC-1683-NB.37-R004 ISNB.M NN57 EL714-11 I-Y N

MC-1683-NB.37-R006 ISNB.M NN57 EL711-11 I

Y N

y MC-1683-NB.37-R010 ISNB.M NN56 EL711-03 It Y

N MC-1683-NB.37-R011 ISNn.M NN57 EL711-03 I

Y N

MC-1683-NC.06-R007 ISNB.M EE52 EL722-11 I

Y N

MC-1683-HV.04-R015 ISNB.M MM54 EL744-06

I N

N MC-1683-NV.06-R009A ISNB.M JJ51 EL734-10 I

Y N

MC-1683-NV.06-R012A 2SNB.M JJ51 EL734-01 I

Y N

MC-1683-NV.06-R023A ISNB.M JJ50 EL735-03 I

Y N

MC-1683-NV.11-R020 ISNB.M KK54 EL724-00 I

Y N

p MC-1683-NV.16-R007 ISNB.M LL51 EL745-02 I

Y N

1. -MC-1683-NV.50-R002 ISNB.M KK53 EL741-02 I

Y N

m h

1. -MC-1683-NV.53-R009 ISNB.M LL53 EL742-09 I

Y N

g

1. -MC-1683-NV.58-R006 ISNB.M KK50 EL745-01 I

Y N

1. -Exempted from periodic functional testing.

I l

l

{

TABLE 3.7-4b

~

c SAFETY RELATED MECHANICAL SNUBBERS

• F HIGH RADIATION l

N ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT l

P1PE SUPPORT 1(PE/QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE w

l Ms 1683-NV.59 R006 ISNB.M JJ52 EL745-06 I

Y N

MC-1683-NV.63-R001 1SNB.M KK54 EL742-03 I

N N

l MC-1683-NV.64-R001 ISNB.M KK54 EL741-05 I

N N

MC-1683-RV.01-R005A 2SNB.M PP54 EL778-09 A

N N

MC-1683-RV.02-R003 ISNB.M FF54 EL728-03 A

N N

MC-1683-VI.12-R034 ISNB.M FF53 EL741-06 I

Y N

MC-1683-VI.12-R035 ISNB.M FFS2 EL743-09 I

Y N

MC-1683-VI.12-R036 ISNB.M JJ50 EL743-09 I

Y N

l MC-1683-VI.21-3017 ISNB.M 0D44 EL769-08 A

N N

R MC-1683-VI.21-R021 ISNB.M EE44 EL793-07 A

N N

l MC-1683-VI.21-R022 ISNB.M EE44 EL794-04 A

N N

l 7

MC-1683-VI.21-R023 ISNB.M EE44 EL749-07 A'

N N

l MC-1683-VI.21-R024 ISNB.M EE44 EL792 A.

N N

MC-1683-VI.21-R025 ISNB.M EE44 EL793-04 A'

N N

MC-1683-VI.21-R026 ISNB.M EE44 EL793-07 A

N N

MC-1683-VI.21-R030 ISNB.M EE44 EL791-09 A

N N

IA N

N MC-1683-VI.21-R032 ISNB.M EE44 EL717-06 MC-1683-VI.22-R006 ISNB.M EE53 EL799-06 A

N N

l MC-1683-VI.22-R007 ISNB.M EE53 EL799-06 A.

N N

MC-1683-VI.22-R008 ISNB.M EE53 EL799-06 A

N N

MC-1583-VI.27-2009 ISNB.M EE53 EL799-06 A

N N

MC-1683-VI.22-R013 ISNB'. M _

EES3 EL784-06 A

N_

N MC-1683-VI.22-R015 ISNB.M EES3 EL791-10 A

N N

MC-1683-VI.2D R018 ISNB.M EES3 EL795-10 A

N N

l MC-1683-VI.22-R022 ISNB.M EE53 EL795-10 A

N N

c._

l 5

l l

m f

TABLE 3.7-4b 5g SAFETY RELATED MECHANICAL SNUBBERS

• HIGH RADIATION r

ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT H

PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN ** -

TO REMOVE MC-1683-VI.22-R024 ISN3.M EE53 EL799-06 A

N N

MC-1683-VI.25-R-012 ISNB.M BBA42 EL754-08 A

N N

MC-1683-WG.11-R004A ISNB.M NN53 EL725-06 I

Y N

MC-1683-WG.38-R002 ISNB.M MM52 EL724-00 I

N N

MC-1683-WL.05-R013 ISNB.M MM58 EL723-00 I

N N

MC-1683-WL.13-R007 ISNB.M LL61 EL727-00 I

N N

MC-1683-WL.23-R004 ISNB.M LL60 EL715-03 I

Y N

MC-1683-WL.23-R009 1SNB.M LL60 EL711-03 I

Y N

MC-1683-WL.23-R010 ISNB.M LL60 EL712-00 I

Y N-Ri MC-1683-WL.23-R011 ISNB.M LL60 EL711-03 I

Y N

1-MCA-AS-H216 ISNB.M NN52 EL763-00 A'

N N

l' 1-MCA-AS-H372 ISNB.M MM52 EL7G3-00 A

N N

1-MCA-BB-H326 ISNB.M FF53 EL734-03 I;

Y N

1-MCA-BB-H330 ISNB.M EE53 EL737-09 I

Y N

1-MCA-BB-H339 ISNB.M FF53 EL744-06 I

Y N

1-MCA-BB-H352 2SNB.M FF52 EL736-08 iI Y

N 1-MCA-BB-H361 ISNB.M FF53 EL738-09 I

Y N

1-MCA H378 ISNB.M EES3 EL738-09 Y

N 1-MCA-BB-H381 ISNB.M FF52 EL74C-08 Y

N 1-MCA-BB-H394 ISNB.M FF52 EL739-09 L

Y N

1-MCA-CA-H159 ISNB.M EE44 EL759-06 A

N N

1-MCA-CA-H3T5 ISNB.M BB60 EL724-00 A

N N

1-MCA-CA-H347 ISNB.H BB51 EL727-09 A

N N

1-MCA-CA-H349 ISNB.M 8B51 EL727-09 A

N N

1-MCA-CA-H415 ISNB.M EES2 EL759-06 A

N N

I c_

1-MCA-CA-H419 ISNB.M EE52 E1579-06 A

N N

EE 1-MCA-CA-H459 ISNB.M 0045 EL756-03 A

N N

1-MCA-CA-H464 2SNB.M EE44 EL759-06 A

N N

(

g TABLE 3.7-4b 2

SAFETY RELATED MECHANICAL SNUBBERS *

-c

~ '

HIGH RADIATION 5

ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT

[

PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE

~

1-MCA-CA-H467 ISNB.M EE44 EL759-06 A

N N

1-MCA-CA-H498 ISNB.M 0053 EL756-06 A

N

.N 1-MCA-CF-H292 2SNB.M 0053 EL755-09 A

N N

1-MCA-CF-H293 ISNB.M DD53 EL765-00 A

N N

1-MCA-C.F-H320 ISNB.M EE52 EL755-03 A

N N

1-MCA-CF-H340 ISNB.M EE44 EL759-09 A

N N

1-MCA-CFI-5660 1SNB.M EE53 EL753-00 A

N N

1-MCA-CFI-5680 ISNB.M EE44 EL754-03 A

N N

1-MCA-FW-H109 ISNB.M HH53 EL718-00 1

N N

1-MCA-FW-Hill ISNB.M KK53 EL721-07 I

Y N

1-MCA-FW-H124 ISNB.M' HH55 EL697-06 I

N N

w 1-MCA-FW-H128

'1SNB. M KK51 EL761-05 A.

N N

1 1-MCA-FW-H130 2SNB.M KK53 EL761-00 A

N N

u l-MCA-FW-H131 3SNB.M KK53 EL757-00 A

N N

1-MCA-FW-H194 ISNB.M KK53 EL761-01 A

N N

1-MCA-KC-H344 ISNB.M KK53 EL759-09 I

Y N

1-MCA-KC-H804 ISNB.M MM61 EL718-06 I

Y N

l'-MCA-KC-1023 ISNB.M JJ57 EL767-07

'A N

N 1-MCA-KC-1062 1SNB.M MM53 EL759-03 A

N N

1-MCA-KC-1092 2SNB.M HH57 EL744-09 A

N N

1-MCA-KC-1095 ISNB.M HH56 EL742-00 A

N N

1-MCA-KC-2130 ISNB.M HH55 EL741-10 A

N N

p 1-MCA-KC-2133 ISNB.M HH56 EL740-07 A

N N

m E

1-MCA-KC-2135 ISNB.M HH57 EL740-07 A

N N

?t, 1-MCA-KC-2321 2SNB.M LL53 Et759-03 A

N N

A 1-MCA-KF-1043 ISNB.M PP51 EL759-03 A

N N

1-MCA-KF-1045 ISNB.M PPS1 EL759-03 A

N N

P 1-MCA-KF-2099 2SNB.M PP51 EL756-08 A

N N

u l-MCA-NB d907 ISNB.M

-NN56 EL727-05 A

N N

1-MCA-NB-H908 ISNB.M NN56 EL724-10 A

N N

1-MCA-NB-H917 ISNB.M LL51 EL740-00 I

Y N

N l

[5 SAFETY RELATED MECHANICAL SNUBBERS

• TABLE 3.7-4b m

HIGH RADIATION

?

ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT w

PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN ** -

TO REMOVE 1-MCA-NB- !!919 ISNB.M LL51 EL745-06 I

Y N

1-MCA-NB-H935 2SNB.M KK51 EL739-06 I

Y N

1-MCA-NB-1012 2SNB.M NN56 EL741-05 I

Y N

1-MCA-NB-1036 ISNB.M PP56 EL744-06 I

Y N

1-MCA-NB-1319 ISNB.M JJ51 EL746-06 I

Y N

1. -1-MCA-NB-2337 2SNB.M QQS6 EL744-06 I

Y N

1. -1-MCA-NB-2342 ISNB.M QQ56 EL749-06 I

Y N

1. -1-MCA-NB-2343 2SNB.M PP56 EL745-01 I

Y N

1. -1-MCA-NB-2351 2SNB.M QQ56 EL744-06 I

Y N

R 1-MCA-NB-2358 1SNB.M QQS6 EL744-07 I

Y N

1-MCA-NB-2385 2SNB.M PP56 EL742-06 I'

Y N

Y 1-MCA-NB-2386 ISNB.M PPS6 EL742-06 I

Y N

1-MCA-MC-H027 ISNB.M FF52 EL738-00 I

Y N

1-MCA-NC-11059 ISNB.M FF52 EL738-00 I

Y N

1-HCA-NC-H063 ISNB.M Hil52 EL738-05 I

Y N

1-MCA-NC-H064 ISNB.M HH52 EL738-04

I Y

N 1-MCA-ND-H035 ISNB.M LL52 EL740-10 I

N N

1-MCA-ND-H110 ISNB.M GG53 EL696-09 I

N N.

1-MCA-ND-H176 ISNB.M Hil53 EL726-00 I

Y N

1-MCA-ND-H177 ISNB.M HH53 EL724-00 I

Y N

1-MCA-ND-H251 ISNB.M llH53 EL708-00 I

N N

1-MCA-ND-H260 ISNB.M GG53 EL724-00 I

Y N

1-MCA-ND-H295 ISNB.M MMS 2 EL735-00 I

Y N

1-MCA-ND-H324 ISNB.M HH52 EL728-09 I

i N

1-MCA-ND-H325 ISNB.M HH52 EL729-09 I

Y N

E:

1. -Exempted from periodic functional testing.

N._.

v

.x h

TABLE 3.7-4b SAFETY RELATED MECHANICAL SNUBBE'RS*

Eq HIGH RADIATION ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE' SHUTDOWN *A

.TO REMOVE 1-MCA-ND-H326 ISNB.M HH53 EL728-00 I

Y N

1-MCA-ND-H327 2SNB.M HH53 EL726-08 I

Y N-1-MCA-ND H331 ISNB.M JJ52 EL726-00 I

Y N

1-MCA-ND-H333 ISNB.M LL51 EL740-10 I

N N-1-MCA-NI-H101 ISNB.M HH52 EL752-08 I

N N

1-MCA-NI-H316 1SNB.M HH52 EL761-00 A

N N

1-MCA-NI-H357 ISNB.M FF53 EL716-00 I

Y N

1-MCA-NI-H360 ISNB.M JJ53 EL763-00 A

N N'

1-MCA-NI-H364

~1SNB.M KK53 EL770-01 A

'N N

1-MCA-NV-H215

,ISNB.M LL55 EL723-03 A

N

.N us 1-MCA-NV-H310 ISNB.M JJ52 EL726-01 I

5 1-MCA-NV-H5578 ISNB.M EE52 EL736-09 I

Y N

Y N

y 1-MCA-NV-H5587 ISNB.M HH52 EL736-09 I

Y N

on 1-MCA-NV-H5589 ISNB.M JJ51 EL740-06 I

Y N

1-MCA-NV-H5591 ISNB.M JJ52 EL741-01' I

Y-

,N 1-MCA-NV-H5593 ISNB.M JJ52 EL741-01 I

Y N

~ 1-MCA-NV-H5595 ISNB.M JJ51 EL741-01 I

Y N

1-MCA-NV-H5602 ISNB.M KK51 EL742-06 I

Y N

1-MCA-NV-H5603 ISNB.M MM56 EL722-06 A

N N

1-MCA-NV-H5605 ISNB.M GG53 EL740-09 I

Y N

y 1-MCA-NV-H560P 1SNB.M KK52 EL728-09 I

Y N

=

1-MCA-NV-H5609 ISNB.M JJ53 EL724-07 I

Y N

h 1-MCA-NV-H5617 ISNB.M FF53 EL745-08 A

N N

a 1-MCA-NV--H5619 ISNB.M KK53 EL723-07 I

Y N

5 1-MCA-NV-'H5621 2SNB.M JJ59 EL726-00 I

Y N

1-MCA-NV-H5622 2SNB.M JJ55 EL724-00 I

Y, N

1-MCA-HV-H5624 ISNB.M

,JJ53 EL721-02.

I Y

N u

l-MCA-NV-H5625 ISNB.M JJ53 EL724-06 I

Y-N

s 00 if TABLE 3.7-4b 8

{

SAFETY RELATED MECilANICAL SNUBBERS

• EE Ei HIGH RADIATICN ACCESSIBLE /

ZONE DURING.

ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN **

TO REMOVE s

1-MCA-NV-H5630 ISNB.M NN56 EL740-05 I

Y N

1-MCA-NVI-6340 ISNB.M JJ54 EL716-00 A

N N

1-MCA-RN-H937 ISNB.M FF55 EL724-06 A

N N

1-MCA-RN-H941 ISNB.M FF58 EL735-06 I

Y N

1-MCA-RN-H956 ISNB.M FF54 EL743-08 I

Y N

1-MCA-RN-H959 ISNB.M GG52 EL737-05 I

Y N

1-MCA-RN-0974 ISNB.M GG52 EL728-10 I

Y N

1-MCA-RN-1053 ISNB.M FF54 EL745-00 I

Y N

1-MCA-RN-1180 ISNB.M FF54 EL741-06 I

Y N

1-MCA-RN-1305 ISNB.M FF52 EL735-06 I

Y N

1-MCA-RN-1323

,1SNB.M EE59 EL724-00 I

Y N

if 1-MCA-RN-1500 ISNB."

FF56 EL724-06 A'

N N

^

1-MCA-RN-1529 l#: t EE59 EL737-08 I

Y N

Td 1-MCA-RN-1530 1-FF59 EL737-06 I

Y N

E]

1-MCA-RN-1533 2SNB.M FF59 EL732-00 I

Y N

1-MCA-RN-2467 ISNB.M FF53 EL738-00 I

Y N

1-MCA-RN-2468 ISNB.M EE53 EL729-05 II Y

N 1-MCA-RN-2469 ISNB.M EE53 EL731-06 I

.Y N

1-MCA-RN-2492 ISNB.M MM52 EL744-00 A

Y N

1-MCA-RN-2510 ISNB.M EES3 EL731-00 I

Y N

1-MCA-RN-2511 4SNB.M EES3 EL731-00 A

Y N

3" 1-MCA-RV-H184 ISNB.M NN56 EL770-06 A

N N

1-MCA-RV-H187 ISNB.M NN56 EL767-00 A

N.

N 1-MCA-RV-H188 ISNB.M QQ52 EL778-06 A

N N

1-MCA-RV-H192 ISNB.M QQ52 EL773-11 A

N N

r*

1-MCA-RV-H197 ISNB.M NN56 EL779-03 A

N N

EF 1-MCA-RV-H203 ISNB.M QQ52 EL777-06 A

N N

1-MCA-SA-H022 ISNB.M EE53 EL777-08 A

N N

'd 1-MCA-f4-H023 ISNB. M EE53 EL776-07 A

N N-

[

TABLE 3.7-<b 5

p; SAFETY RELATED MECHANICAL SNUBBERS

• C-a P

HIGH RADIATION ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT s

PIPE SUPPORT TYPE /QUAN.

LOCATION INACCESSIBLE SHUTDOWN"* -

TO REMOVE

1. -1-MCA-SA-H025 ISNB.M EE53 EL718-08 I

Y N

1-MCA-SA-H026 ISNB.M EES3 EL728-00 I

Y N

1-MCA-SA-H027 ISNB.M D053 EL727-09 I

Y' N

1-MCA-SA-H032 ISNB.M DD53 EL729-06 A

N N

1-MCA-SA-H039 ISNB.M AA53 EL727-09 A

N N

1-MCA-SA-H107 ISNB.M AA53 EL718-02 A

N N

1-MCA-SM-H017 ISNB.M GG43 EL760-06 A

N N

1-MCA-SM-H076 ISNB.M GG53 EL760-06 A

N N

1-MCA-SM-H101 ISNB.M GG44 EL760-06 A

N N

t' 1-HCA-SM-H164 ISNB.M

'GG53 EL760-06 I

Y N

1-MCA-SM-H194

'1SNB.M 0043 EL780-04 A,

N N

l' 1-MCA-SM-H202 ISNB.M EE43 EL795-03 A

N N

as 1-MCA-SM-H203 ISNB.M EE53 EL795-04 A.

N N

1-MCA-SM-H204 ISNB.M EE53 EL795-04 A

N N

1-MCA-SM-H205 ISNB.M EE44 EL795-04 A

N N

1-MCA-SV-H001 ISNB.M GG44 EL795-00

,A N

N 1-MCA-SV-H006 ISNB. M GG43 EL795-00

'A N

N 1-MCA-SV-H011 ISNB.M GG53 EL795-00 A

N N

1-MCA-WL-H479 2SNB.M KK61 EL726-00 I

Y N

1-MCA-YC-0181, ISNB.M GG57 EL774-09 A

N N

1-MCA-YC-0189 ISNB.M FF58 EL776-08 A

N N

1-MCR-BB-H001 ISNB'.M C 210 38-00 743-04 I

Y N

1-MCR-BB-H071 ISNB.M D 349 37-10 46-05 I

Y N

1-MCR-BB-0500 ISNB.M C 185 00-00 730-03 I

Y N

1-MCR-BB-0522 ISNB.M C 137 54-00 729-03 I

Y

.N gg 1-MCR-88-0523 ISNB.M B 180 56-09 731-03 I

Y N

1. -Exempted from periodic functional testing.

3 y.,

1 g^

ks s

%s g

7f

.s

e

.m

\\

i

'1:

2 Q

-l w.

'{

~.

1 TABLE 3.7-4b 3

g c

y e

+;

\\, z SAFETY RELATED MECHANICAL SNUBBERS *' S ~ ?y:d i, s, ,s r.< 1 7 e e MIGH RADIATION ^ ISPECIALLY DIFFIC / m- ? ACCESSIBLE / cZONE DURI E w PIPE SUPPORT TYPE /QUAN. LOCATION INACCESSIBLE SHUTDOWJ**j 3 ,TO REMOVE -t ?1 1-MCR-BB-C716 ISNB.M C 207 36-06 745-08 I .Y J N N 'N 3-N /' ' 1-MCR-BB-0717 2SNB.M C 204 38-10 745-03 I Y y g 1 N 1-MCR-BB-0718 ISNB.M C 203 40-11 748-08 I Y g N 1-MCR-BB-0719 ISNB.M C 203 40-11 748-08 I Y 1-MCR-3B-0721 .1SNB.M C 198 40-09 738-00 I Y e 'N'- . <- N 1-MCR-BB-0725 ISNB.M C 213 36-04 746-02 I Y 1-MCR-BB-0726 ISNB.M C 215 35-10 744-04 I 'Y ,} N 1-MCR-BB-0727 ISNB.M C 215 35-10 744-07 Y .: m^ ,N 1 1-MCR-BB-0729 ISNB.M C 212 38-07 744-00 I -Y N R 1-MCR-BB-0730 LISNB.M C 211 38-06'743-03 I .Y N 1-MCR-BB-0732 ISMB.M C 207 36-08 743-03 I, Y N b T 1-MCR-BB-0733 ISNB.M C 208 35-08 743-03 I Y N 1-MCR-BB-0734 ISNB.M C 240 36-01 743-03 I: N N 1-MCR-BB-0735 ISNG.M C 212 37-09 744-06 I Y N 1-MCR-BB-0736 ISNB.M C 212 37-09 745-03 I Y N I Y N 1.-MCR-8B-0738 ISNB.M C 207 36-08 747-02 1-MCR-BB-0739 ISNB.M C 207 36-08 747-0?' I 'Y N 1-MCR-BB-0751 ISNB.M C 192 40-06 732-08 I Y N 1-MCR-BB-0752 ISNB.M C 192 40-06 732-08 I Y N 1-MCR-BB-0753 ISNB.M 1.C 183 40-06-736-00 I Y' N 1-MCR-BB-0760 ISNB.M B 153 40-09 742-05 I Y N. 1-MCR-BB-0761 ISNB.M B 153 40-09 742-01 I Y N 1-MCR-BB-0762 ISNB.M B 157 38-07 743-04 I Y N 1-MCR-BB-0763 ISNB.H B 158 38-03 746-03 I Y N 1-MCR-BB-0765 1SNB.M B 153 38-10 746-06 I Y N h 1-MCR-CB-0766 ISNB.M B 153 38-10.747-09 I Y N se 1-MCR-BB-0767 ISNB.M B 153 38-10 748-00 I Y N 1-MCR-BB-0769 ISNB.M B 147-3E-04 748-07 I Y .N 1-MCR-BB-0770 .1SNB.M B 145 35-04 745-10 I Y. N

• o 1-MCR-BB-0771 ISNB.M B 142 34-05 745-10 I

Y N.' ~ 3 1-MCR-BB-0772 ISNB.M B 151 41-02 747-06 I Y N ~_.

.~ r ue j) TABLE 3.7-4b SAFETY RELATED MECHANICAL SNJBBERS* p E! El HIGH RADIATION ACCESSIBLE / ZONE DURING ESPECIALLY DIFFICULT l PIPE SUPPORT TYPE /QUAN. LOCATION INACCESSIBLE SHb'90WN** TO REMOVE 1-MCR-BB-0774 ISNB.M B 14G 28-06 749-07 I Y N i 1-MCR-BB-0775 ISNB.M B 152 38-OL 747-11 I Y 'N 1-MCR-BB-0776 ISNB.M B 152 36-02 748-07 I Y N 1-MCR-BB-0777 ISNB.M B 157 41-01 746-00 I Y N 1-MCR-BB-0778 ISNB.M B 159 38-02 746-06 I Y N I 1-MCR-BB-0780 ISNB.M B 153. 41-00 746-04 I Y N l-MCR-BB-0781 ISNB.M B 153 39-09 746-00 I Y N 1-MCR-BB-0783 ISNB.M B 147 35-01 746-00 I Y N 1-MCR-BB-0784 ISNB.M B 147 35-01 746-02 I Y N un 1-MCR-BB-0786 ISNB.M B 162 37-01 746-03 I Y N 3 1-MCR-88-0788 ISNB.M B 155 39-04 748-00 I Y N sa 1-MCR-BB-0790 ISNB.M B 15141-01746-05 I' Y N 5 1-MCR-BB-0792 ISNB.M B 151 41-01 746-10 I Y N 1-MCR-88-0794 ISNB.M B 145 37-00 745-10 I Y N 1-MCR-BB-0797 ISNB.M B 155.38-05 74B-07 I Y N 1-MCR-88-0798 ISNB.M B 151 38-03 746-03 I Y N 1-MCR-88-0799 ISNB.M B 162 37-01 746-08. {I Y N 1-MCR-BB-C313 ISNB.M C 189 53.-05 732-05 I Y N 1-MCR-BB-0814 ISNB.M C 189 52-09 730-03 1 Y N 1-MCR-BWI-5040 2SNB.M D 337 31-03 810-00 I Y N ~ 1-MCR-BWI-5050 2SNB.M C 200 31-03 810-00 I Y N 1-MCR-BWI-5060 2SNB.M B 155 31-03 810-00 I Y N-2p 1-MCR-BWI-5070 2SNB.M A 020 31-03 810-00 I Y N E 1-MCR-CA-H392 ISNB.M C 251 21-08 744-10 I Y N EI 1-MCR-CA-H398 ISNB.M FF50 EL769-06 I Y N E 1-MCR-CA-H401 ISNB.M FF51 EL766-09 I Y N 1-MCR-CA-H448 ISNB.M FF47 EL774-04 I Y N Ei 1-MCR-CA-H484 ISNB.M FF46 EL766-09 I Y N 1-MCR-CA-H490 2SNB.M A 024 22-05 773-06 I Y N l-MCR-CA-H514 ISNB.M B 184 55-06 752-06 I Y N 1-MCR-CA-H515 ISNB.M A 005 55-06 752-06 I Y N 1-MCR-CF-H175 ISNB.M A 070 40-10 773-00 I Y N 1-MCR-CFI-5620 2SNB.M B 145 31-03 750-00 I Y N

i a v TABLE 3.7-4b C SAFETY RELATED MECHANICAL SNUBBERS

• e E

HIGH RADIATION l 3 ACCESSIBLE / ZOME DURING ESPECIALLY DIFFICULT PIPESUPP0M TYPE /QUAN. LOCATION INACCESSIBLE SHUTDOWN ** _ TO REMOVE l e l 1-MCR-NM-0716 ISNB.M B 168 11-06 749-07 I Y .N l 1-MCR-NM-0726 ISNB.M D 355 22-00 748-02 I Y N 1-MCR-NM-0728 ISNB.M D 355 22-00 748-01 I Y N l L 1-MCR-NM-0729 ISNB.M D 355 22-00 741-04 I Y N l 1-MCR-NM-0730 ISNB.M D 355 32-00 740-05 I Y N l 1-MCR-NM-0731 2SNB.M D 355 32-00 740-07 I Y N l 1-MCR-NM-0732 ISNB.M D 355 22-01741-06 I Y N 1-MCR-NM-0758 ISNB.M B 114 45-06 750-00 I Y N 1-MCR-NM-0761 4SNB.M B 114 45-00 750-00 I Y N R 1-MCR-NM-0762 1SNB.M B 114 45-09 756-04 I Y N 1-MCR-NV-0634 ISNB.M D 351 56-00 726-09 I. Y N T 1-MCR-NV-0701 ISNB.M C 187 56-09 729-00 I Y N l C 1-MCR-HV-0720 ISNB.M C 230 40-01 734-10 I Y N l 1-MCR-HV-0721 ISNB.M C 230 47-06 733-00 I Y N E 1-MCR-HV-C722 ISNB.M C 230 47-06 733-00 I Y N 1-MCR-HV-0723 ISNB.M C 227 27 08 737-06 I Y N

• I Y

N 1-MCR-NV-0724 ISNB.H C 227 27 08 737-09* 1-MCR-NV-0819 ISNB.M C 216 40-00 737-10 I Y N 1 1-MCR-NV-0874 ISNB.M C 238 32-05 745-00 I Y N 1-MCR-NV-0875 ISNB.M C 240 32-11 746-02 I Y N l-1-MCR-NV-0928 ISNB.M D 315 34-09 745-02 I Y N 1-MCR-NV-0929 2SNB.M D 317 33-00 746-00 I Y N 1-MCR-NV-0940 ISNB.M A 060 35-09 745-02 I Y N 1-MCR-HV-094? ISNB.M A 061 35-04 746-01 I Y N 1-MCR-NV-09*6 ISNB.M B 134 36-09 744-06 I Y N 1-MCR-NV-0978 ISNB.M D 317 32-05 749-03 I Y -N c_ E 1-MCR-NV-1002 ISNB.M B 108 47-06 734-00 I Y' N 1-MCR-NV-1003 ISNB.M B 108 47-06 734-00 I Y N

q. %. *

~ 1 ~ pp TABLE 3.7-4b a Si SAFETY RELATED MECHANICAL SNUBBERS * ?? i c: HIGH RADIATION 55 ACCESSIBLE / ZONE DURING ESPECIALLY DIFFICULT j, PIPE SUPPORT TYPE /QUAN. LOCATION INACCESSIBLE SHUTDOWN ** TO REMOVE 1-MCR-NV-1050 2SNB.M D 30140-11 730-00 $77-I Y N 4 1-MCR-NV-1054 ISNB.M D 301.37-01 740-03 ~ I Y N 1-MCR-NV-1062 15NB.M B 101 33-09 738-06 I Y N 1-MCR-NV-1073 ISNB.M D 299 40-00 732-06 I Y N 1-MCR-NV-1074 ISNB.M D 299 55-11 732-06 I Y N 1-MCR-NV-1079 2SNB.M B 133 50-05 730-03 I Y N 1-MCR-NV-1095 ISNB.M B 114 47-06 732-10 I Y N 1-MCR-NV-1096 ISNB.M B 114 47-06 732-00 I Y N 1-MCR-NV-1202 ISNB.M B 124 52-00 734-01 I Y N 1-MCR-HV-1207 ISNB.M B 124 55-02 730-03 I Y - N 1-MCR-NV-1220 1SNB.M B 157 53-08 731-07 I Y N e, 1-MCR-NV-1230 ISNB.M C 230 56-00 730-03 I Y N 3; 1-MCR-NV-1234 ISNB.M C 230 49-00 730-03 I Y N -a 1-MCR-NV-1237 ISNB.M C 230 39-02 733-01 I Y N 5, 1-MCR-NV-1238 2SNB.M C 230 39-02 732-05 I Y N 1-MCR-NV-1247 ISNB.M B 101 50-10 733-04 I Y N 1-MCR-NV-1263 ISNB M C 186 55-06 729-10 I Y N i 1-MCR-HV-1290 ISNB.M D 306 36-10 734-11' I Y N 1-MCR-NV-1291 ISNB.M D 306 36-10 735-01 I Y N 1-MCR-NV-1293 ISN3.M D 306 37-07 731-00 I Y N 1-MCR-RN-0670 ISNB.M B 114 41-00 749-11 I Y N 1-MCR-RV-0585 2SNB.M D 331 55-04 736-02 I Y N 37 1-MCR-RV-0648 ISNB.M C 261 56-01 825-03 I N N m.a 1-MCR-RV-0649 ISNB.M C 261 55-03 827-06 I N N M 1-MCR-RV-0685 ISNB.M C 261 56-01 823-11 I N N A 1-MCR-RV-0686 ISNB.M C 258 56-00 826-00 I N N 1-MCR-RV-0726 ISNB.M C 265 56-00 822-01 I N N P 1-MCR-RV-0727 ISNB.M C 265 56-00 822-05 I N N I 1-MCR-RV-0758 ISNB.M C 265 56-00 825-07 I N N sa 1-MCR-S-KC-119-01-N ISNM.M D 244 54-11 742-05 I N N 1-MCR-S-KC-120-01-NN ISNB.M C 208 54-06 756-09 A Y N

' j( TA3LE 3.7-4b C j SAFETY RELATED MECHANICAL SNUBBERS

• Ei HIGH RADIATION

1 ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN. LOCATION INACCESSIBLE SHUTDOWN ** TO REMOVE 1-MCR-S-KC-120-02-NN ISNB.M A 089 21-10 734-00 I Y N 1-MCR-S-KC-120-02-00 ISNB.M D 304 27-04 736-07 I Y .H 1-MCR-S-KC-121-01-AA ISNB.M B 158 57-00 749-06 I Y N 1-MCR-S-KC-121-04-BB ISNB.M B 091 20-01 734-00 I Y N 1-MCR-S-KC-121-04-CC ISNB.M D 310 22-09 736-07 I Y N 1-MCR-5-NC-112-01-B ISNB.M C 248 55-10 744-02 I Y N 1-MCR-S-NC-112-01-C 1SNB.M C 248 56-01 744-02 I Y N 1-MCR-S-NC-112-01-0 2SNB.M C 248 56-06 744-02 I Y N 1-MCR-5-NF-100-01-E ISNB.M C 232 59-10 815-03 A N N 1-MCR-S-NF-100-01-X ISNB.M C 250 53-04 814-10 I N N 1-MCR-5-NF-101-01-U 1SNB.M C 250 53-00 822-00 A N N dd 1-MCR-S-HI-100-01-D ISNB.M C 214 53-08 749-09 I' Y N 1-MCR-S-NI-100-04-L ISNB.M B 143 48-03 749-06 I Y N 7' 1-MCR-S-NI-100-04-Y ISNB.M B 151 55-09 730-03 I! Y N C; 1-MCR-S-NI-100-07-B ISNB.M A 034 53-07 749-09 I Y N 1-MCR-S-NI-100-08-T ISNB.M D 321 55-09 728-10 I Y N 1-MCR-S-NI-100-09-D ISNB.M C 240 54-00 729-09

I Y

N 1-MCR-S-NI-100-09-H ISNB.M C 240 54-05 733-02 I Y N 1-MCR-S-NI-105-01-T ISNB.M C 200 30-09 809-10 A N N 1-MCR-S-NI-105-01-U ISNB.M C 190 52-00 735-00 I Y N 1-MCR-S-NI-105-01-V ISNB.M C 190 52-00 734-09 I Y N 3" 1-MCR-5-NI-105-02-SS ISNB.M A 023 31-08 809-10 A N N 1-MCR-S-NI-105-02-TT ISNB.M A 023 31-08 809-10 A N N 1-HCR-S-N I-105-03-SS ISNB.M D 270 30-11 809-10 A N N g 1-MCR-S-NI-105-03-TT ISNB.H D 290 30-11 809-10 A N N 1-MCR-S-NI-105-04-Q ISNB.M B 156 47-00 809-10 A N N 1-MCR-S-NI-100-02-AA ISNB.M C 239 52-06 742-06 I N N 1-MCR-5-NI-100-08-X ISNB.M 0 318 45-00 730-03 I Y N 'd 1-MCR-5-NI-105-01-W ISNB.M C 189 47-00 734-03 I Y N

3: h TABLE 3.7-4b ~ SAFETY RELATED MECHANICAL SNUBBERS

• E._,

H HIGH RADIATION ACCESSIBLE / ZONE OURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN. LOCATION INACCESSIBLE SHUT 00WN**, TO REMOVE 1-NCR-S-NI-105-04-R ISNB.M B 156 47-00 809-10 A N .N 1-MCR-S-HI-105-04-5 ISNB.M C 187 51-07 731-11 I Y N 1-MCR-S-NI-105-04-T ISNB.M C 187 50-03 731-08 I Y N 1-MCR-S-NM-100-01-R ISNB.M C 209 56-00 733-11 I Y N 1-MCR-S-RF-100-01-B 2SNB.M C 242 5'4-05 746-09 I Y N 1-MCR-S-RV-100-01-L ISNB.M A 056 46-05 731-10 I Y N 1-MCR-S-RV-100-02-8 ]SNB.M A 080 57-00 735-03 I Y N 1-MCR-S-RV-100-02-5 ISNB.M A 080 51-06 740-09 I N N 1-MCR-S-RV-101-01-AA ISNB.M A 053 52-02 734-00 I Y N 1-MCR-S-RV-101-02-J ISNB.M B 119 57-00 752-06 I Y N 1-MCR-S-SM-100-01-A 1SNB.M C 200 30-09 809-10 A N N Y 1-MCR-S-VE '_01-01-G ISNB.M C 215 57-06 777-11 I' N N [ 1-MCR-S-VE-101-01-L ISNB.M C 215 54-06 761-06 I Y N 1-MCR-S-VE-101-01-5 ISNB.M C 215 57-06 762-09 A Y N

5 1-MCR-S-VE-102-01-F 1SNB.M C 236 56-08 744-02 I

Y N 1-MCR-S-VI-100-01-K ISNB.M C 26161-07 797-06 I N N 1-MCR-S-VI-100-01-0 ISNB.M C 258 56-02 799 iI N N 1-MCR-5-VI-100-01-T ISNB.M C 262 61-01 763-07 I N N 1-MCR-S-VI-100-01-U ISNB.M C 262 61-01 760-00 I N N 1-MCR-S-VI-100-01-Z ISNB.M C 264 61'00 760-00 I N N 1-MCR-S-VI-102-02-BB ISNB.M B 116 37-08 759-00 I Y N E 1-MCR-S-VI-102-02-N ISNB.M B 116 38-02 759-00 I Y N 1-MCR-S-VX-100-01-PP ISNB.M C 258 56-09 828-02 I N N 1-MCR-S-WL-102-02-K ISNB.M A 089 25-04 738-06 I Y N 1-MCR-S-WL-103-01-W ISNB.M C 249 50-07 726-10 I Y N 1-MCR-SM-H001 ISNB.M A 015 40-09 831-06 I N N E 1-MCR-SM-H009 ISNB.M A 009 38-04 760-07 I Y N 1-MCR-SM-H079 ISNB.M C 264 38-04 760-07 I Y N 1-MCR-SM-H088 ISNB.M 0 354 37-10 808-01 I N N-1-MCR-S-RV-100-01-B ISNB.M B 056 46-05 732-10 I Y N 1-MCR-S-VI-101-01-E ISNB.M A 188 52-09 739-03 I Y N 1-MCR-S-VI-102-02-JJ ISNB.M A 113 36-10 809-06 A Y N 1-MCR-S-WL-104-01-L ISNB.M B 120 45:08 756-09 A Y N

e = _ lh TABLE 3.7-4b g SAFETY RELATED MECHANICAL SNUBBERS

• EE El HIGH RADIATION ACCESSIBLE /

ZONE DURING ESPECIALLY DIFFICULT PIPE SUPPORT TYPE /QUAN. LOCATION INACCESSIBLE SHUT 00WN** TO REMOVE 1-MCR-SM-H089 ISNB.M 0 354 37-11 808-01 I N N 1-MCR-SM-H097 ISNB.M D 354 38-02 760-07 I Y <N 1-MCR-SM-H154 ISNB.M B 171 38-04 760-07 I Y N 1-MCR-SM-H163 ISNB.M B 171 38-02 808-00' I N d 1-MCR-VI-0502 ISNB.M B 128 47-06 761-09 A Y N 1-MCR-VI-0503 ISNB.M B 128 47-06 761-09 A Y N 1-MCR-VQ-0500 1SNB.M C 257 55-11 809-09 I N N 1-MCR-VQ-0501 ISNB.M C 258 55-11 811-09 I N N 1-MCT-CF-H220 ISNB.M IG34 EL751-06 A N N 1-MCT-CF-H245 ISNB.M IG32 EL751-06 A N N 1-MCT-CF-H246 .2SNB.M IG32 EL747-07 A N If 1-MCT-SM-H120 2SNB.M IE33 EL742-08 A N N N 2-MCA-NB-1594 2SNB.M NN61 EL726-09 I N N l' 2-MCA-NB-H009 2SNB.M NN61 EL726-09 I N N 23 2-MCA-NB-H078 ISNB.M QQ56 EL726-00 I N N 2-MCA-NB-H103 ISNB.M NN57 EL7.41-03 A N N 2-HCA-RN-3014 ISNB.M FF58 EL724-06 l A N N 2-MCA-RN-3022 2SNB.M FF58 EL?22-06 A N N " Snubbers may be added to safety.related systems without prior license Amendment to Table 3.7-4b provided E that a revision to Table 3.7-4b is included with the next license Amendnient request.

• • Modifications to this column due to changes in high radiation areas may b e without prior License Et Amendment provided that a revision to Table 3.7-4b is incided with the next License Amendment

{ request. 5

PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9 Each sealed source containing radioactive material either in excess of-100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of greater than cr equal to 0.005 microcurie,s of removable contamination. APPLICABILITY: At all times. ACTION: With a sealed source having removable contamination in excess of the a. above limits, immediately withdraw the sealed source from use and either: 1. Decontaminate and repair the sealed source, or 2. Dispose of the sealed source in accordance with Commission Regulations. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l-SURVEILLANCE REQUIREMENTS ' 4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by: a. The licensee, or b. Other persons sp'ecifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries pe,r test sample. 4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below. a. Sources in use - At least once per six. months for all sealed sources containing radioactive materials. 1. With a half-life greater than :30 days (excluding Hydrogen 3), and l 2. In any form other than gas. McGUIRE - UNIT 1 3/4 7-72 JUN 1981

• r 1^

z TABLE 3.8-1 (Continued) A -CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES C5 Trip Setpoint or

Response

~ Cont.. Rating Time Device Number & Location (Amperes) (Seconds) -System Powered 3, 600 VAC-Press Htr Pwr Pnis (cont'd) Backup Press Htr Pwr Pnl 10-18 Primary Bkr 90 110 @ 270A-Pressurizer Heaters 15, 16 & 40 Backup Fuse 90 N/A Backup Press Htr Pwr Pn1 10-1C Primary Bkr 90 110 @ 270A Pressurizer Heaters 23, 49 & 50 Backup Fuse 90 N/A w2 m MCC SMXG-FSA Jn Primary 8kr 90 110 @ 270A Pressurizer Heaters 28, 55 & 56 Backup Fuse 90 .N/A : Backup Press Htr Pwr Pn1 10-2C Primary Bkr 90 110 0 270A Pressurizer Heaters 33, 61 & 62 Backup Fuse 90 N/A Backup Press Htr Pwr Pn1 10-2D Primary 8kr 90 110 @ 270A Pressurizer Heaters 38, 67 & 68' g Backup Fuse 90' N/A Backup Press Htr Pwr . Pol 10-2E El Primary Bkr 90 110 @ 270A Pressurizer Heaters 43, 73 & 74 S Backup Fuse 90 N/A

23 BBLE3.8-1(Continued) S CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES

o C

= Irip Setpoint or

Response

M Cont. Rating Time Device Number & Location (Amperes) (Seconds)- System Powered 4. 120 VAC-Panelboards IEKVD-12 Primary Bkr 20 40 @ 60A Rad Mon Sys Sample Solonoid Vivs i i Backup Fuse 6-N/A IMISV 5581 & 5583 KRA-22 Primary Bkr 30 45 9 90A Rad Mons IEMF9 & IEMF U Backup Fuse 1 N/A w b ru

1. g

\\ e 2 i ~

s m F RADI0 ACTIVE EFFLUENTS ~ LIQUID HOLOUP TANKS ~ LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. APPLICABILITY: At all times. ACTION: a. .With the quantity of radioactive material in any outside temporary-tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 heers reduce the tank i contents to within the limit. b. The provisions of Specifications.3.0.3 and 3.0.4 are not applicable. 1 ~ i SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the outside temporary tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7. days when radioactive materials are being added to the tank. ( McGUIRE - UNIT'1 3/4 11-7

~ RADIDACTIVE EFFLUENTS CHEMICAL TREATMENT PONDS LIMITING CONDITION FOR OPERATION 3.11.1.5 The quantity of radioactive material contained in each Chemical Treatment Pond shall be limited by the following expression: 264 j < 1.0 excluding tritius and dissolved or entrained noble gases. where, Aj = pond inventory limit for single radiv.iuclide "j", in curies C. = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single 3 radionuclide "j", microcuries/ml V = design volume of liquid and slurry in the_ pond, in gallons 264 = conversion unit, microcuries/ curie per milliliter / gallon. APPLICABILITY: At all times. ACTION: With the quantity of radioactive material in any of the above listert a. ponds exceeding the above limit, immediately suspend all additions of radioactive material to the pond and within 48 hours reduce the pond contents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS ~ 4.11.1.5 The quantity of radioactive material contained in each batch of slurry (used powdex resin) to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative sample of the slurry, and batches to be transferred to the chemical treatment ponds shall be limited by the expression: kCd < 6.0 x 10s P W 0m j pCi/ml J whdre ~ Q. = concentration of radioactive materials in wet, drained slurry (used 3 powdex resin) for radionuclide "j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8 day hal f-li fe. The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-60, in picocuries/ gram. Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent monthly composite analysis (within 3 months). C) = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", in microcuries/ milliliter. McGUIRE - UNIT 1 3/4 11-8 Amendment No. 7 v. n --.~,,--m -,w e -v

~ ADMINISTRATIVE CONTROLS RECORDS 6.5.2.11 Records of NSRB activities shall be prepared, approved and distributed as indicated below: a. Minutes of each NSRB meeting shall be prepared, approved anc' forwarded to the Vice President, Steam Production, and to the Senior Vice-President, Production and Transmistic,n, within 14 days folleving each meeting. b. Reports of reviews encompassed by Section 6.6 '.8 above, shall be prepared, approved and forwarded to the Vice fresident, Steam Production, and to the Senior Vice President, Production and Transmission, within 14 days following completion of the' review. -c. Audit reports encompassed by Section 6.5.2.9 above, shall be forwarded to the Vice President, Steam Production,-and.to the-Senior h ce Presider, Production and Transmission, and to the managem it positions . responsible for the areas audited within 30 days after completior, of the audit. ~ 6.6 REPORTABLE OCCURRENCE ACTION ,,6.6.1 The following actions shall be'taken for REPORTABLE OCCURRENCES: a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9. b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission chall be reviewed by the Station Manager; or by (1) the Operating Superintendent, (2) the Technical Services Superintendent, or (3) the Maintenance Superintendent, as previously designated by the Station Manager; and submitted to the NSRB and the Vice -sident, Steam Production. 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: The unit shall be'placed in at least HOT STANDBY within one hour. a. b. The NRC Operations Center shall be notified by telephone as soon a's possible and in all cases within one hour. The Vice President, Steam Production, and the NSRB shall be' notified within 24 hours. McGUIRE - UNIT 1 6-11

l ADMINISTRATIVE CONTROLS ~ ~ SAFETY LIMIT VIOLAi{Cy (Continued) A Safety Limit Violation Report shall be prepared. The report shall c. be reviewed by the Operating Superintendent and the Station Manager. This report snall describe (1)-applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Vice President, Steam Production, within 14 days of the violation. 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:' The applicable procedures recommended in Appendix "A" of Regulatory a. Guide 1.33, Revision 2, February 1978. b. Refueling operations. Surveillance and test activities of safety related equipment. c. Security Plan implementation. d. e. Emergency Plan implementation. f. Fire Protection Program implementation.

g.,

PROCESS CONTROL PROGRAM implementation. h. OFFSITE DOSE CALCULATION MANUAL implementation. . i. ' Quality Assurance Program for. effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, December 1977. 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved by the Station Manager; or by (1) the Operating Superintendent, (2) the Technical Services Superintendent, or (3) the Maintenance Superintendent, as previously designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures. 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: a. The intent of the original procedure is not altered. McGUIRE - UNIT 1 6-12 Arendment No. 7

t M ADMINISTRATIVE CONTROLS PROCE60.9Ef_3As PROGRAMS (Continued) ~ b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. The change is documented, reviewed and approved by the Station c. Manager; or by (1) the Operating Superintendent, (2) the Technical Services Superintendent, or (3) the Maintenance Superintendent, as previously designated by the Station Manager; within 14 days of implementation. F. 8. 4 The following programs shall be established, implemented, and maintained: a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside con-tainment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levets. The systems include residual heat removal, boron recycle, refueling water, liquid waste, wasta gas, containment spray, safety injection, chemical and volume control, and nuclear sampling. The program shall include the following: (i) Preventive maintenance and periodic visuil inspection requirements, I and (ii) Integrated leak rate test requirements for each system at refueling cycle intervals or less. In-Plant Radiation Mo'itoring b. n A program which will ensure the capability to accurately. determine the 8 airborne iodine concentration in vital areas under accident conditions. This program shall include the following: (i) Training of personnel, (i'i) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment. Secondary Water Chemistry, c. A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include: (i) Identifici Lion of a sampling schedule for the critical variables and control points for these variable, O McGUIRE - UNIT 1 6-13 Amendment flo. 7

e ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) (ii) Identification of the procedures used to measure the values of the .critieri variables, (iii) Ideacification.of process sampling points, including the discharge tne pondenser hot well pump, o 4 (iv) Procedures for the recording and management of data, 4 (v) Procedures defining corrective actions for off-control point chemistry conditions, including procedures for limiting plant operation under transient off-control chemistry conditions of feedwater and steam generator blowdown to < 100 hours, < 24 hours, or < 2 hours for progressively severe out-of-limit secondary water chemistry, and I (vi) A procedure identifying (a) the authority responsible for the inter-pretation of the data, and (b) -the_ sequence.and. timing of administrative events required to initiate corrective,ac, tion. d. Backup' Method for Determining Subcooling Marain i A program which will ensure the capability to accurately monitor the wl Reactor Coolant System subcooling margin. This program shall include the following: (i) Training of personnel, and .f (ii) Procedures for monitoring. e. Postaccident Sampling 1 -A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, I and containment atmosphere samples under accident conditions. The program i shall include the following: I (i) Training'of personnel, 1 (ii) Procedures for sampling and analysis, (iii) ~ Provisions for maintenance of sampling and analysis equipment. Y i McGUIRE - UNIT 1 6-14 b tid

Special Test Program For conducting the special low power test program as described in Section I.G.1 ^ of the Safety Evaluation Report related to the operation of the McGuire Nuclear Station, Supplement Number 4 dated January 1981, the Technical specifications may be excepted as follows: (Test numbers refer to those specified in William O. Parker's letter of October 10, 1981 to Harold R. Denton/ Appendix E "McGuire Nuclear Station - Response to TMI concerns"): Test Technical Specifications 1 2 3 4 5 6 2.1.1 Core Safety Limits X X X X X 2.2.1 Various Reactor Trips Overtemperature AT X X X X X X Overpower AT X X X X X X Steam Generator Level X X X X X X 3.1.1.3 Moderator Temperature Coefficient X 3.1.1.4 Minimum Temperature for Critichlity X 3.3.1 Various Reactor Trips Overtemperature AT X-X X X X X Overpower AT X X X X X X Steam Generator Level X X X X X X 3.3.2 Safety Injection - All X X X X X X automatic functions Auxiliary feedwater automatic start X X X X X X 3.4.4 Pressurizer X X X 3.7.1.2 Auxiliary Feedwater X X 3.8.1.1 AC Power Sources X X 3.8.E.1 AC Onsite Power Distribution X X System 8.3.2.3 DC Distribution System X X 3.10.3 Special Test Exceptions - X Physics Test j McGuire Unit 1 7-1 Amendment No. 7}}